ML20151Y631

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Operational Environ Radiological Surveillance Program 1987 Annual Rept
ML20151Y631
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 12/31/1987
From: Cockfield D
PORTLAND GENERAL ELECTRIC CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
PGE-1006-87, NUDOCS 8805050056
Download: ML20151Y631 (62)
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4 Trojan Nuclear Plant OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM 1987 ANNUAL REPORT g 1

PORTLAND GENERAL ELECTRIC COMPANY PGE-1006-87

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TROJAN NUCLEAR PLANT OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM January through December 1987 May 1988 l l

l Prepared by PORTLAND GENERAL ELECTRIC COMPANY With Analyses by TMA/EBERLINE a

ALBUQUERQUE. NEW MEXICO 4

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TROJAN NUCLEAR PLANT OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM CONTENTS Section Title Page ABSTRACT . . . . . . . . . . . . . . . . . . . . . -

1.0 INTRODUCTION

. . . . . . . . . . . . . . . . . . . 1-1 2.0 SAMPLING AND PROGRAM PROCEDURES. . . . . . . . . . 2-1 2.1 SAMPLING LOCATIONS . . . . . . . . . . . . . . . . 2-1 2.2 SAMPLING PROCEDURES. . . . . . . . . . . . . . . . 2-1 2.2.1 Air Particulate and Radiolodine. . . . . . . . . 2-1 2.2.2 Ambient Radiation Measurements Using TLDs. . . . 2-2 2.2.3 Food Crops . . . . . . . . . . . . . . . . . . 2-2 2.2.4 Milk . . . . . . . . . . . . . . . . . . . . . . 2-2 2.2.5 Well Water . . . . . . . . . . . . . . . . . . . 2-3 2.2.6 Drinking Water . . . . . . . . . . . . . . . . 2-3 2.2.7 Shoreline Soil . . . . . . . . . . . . . . . . . 2-3 2.2.8 Aquatic Animal . . . . . . . . . . . . . . . . . 2-4  ;

2.3 YEARLY AGRICULTURAL SURVEY WITHIN 5-MILE RADIUS OF TROJAN. . . . . . . . . . . . . . . . . . . . 2-4 3.0 ANALYTICAL PROCEDURES AND COUNTING METHODS . . . . 3-1 3.1 ANALYTICAL DETECTION LIMITS AND COUNT RATE ERRORS. 3-1 3.2 AIR PARTICULATES . . . . . . . . . . . . . . . . . 3-1 3.3 RADIOIODINE. . . . . . . . . . . . . . . . . . . . 3-2 j 3.4 DRINKING AND WELL WATER. . . . . . . . . . . . . . 3-2 )

t 3.5 SHORELINE SOIL . . . . . . . . . . . . . . . . . . 3-2 i

3.6 FISH, INVERTEBRATES, AND FOOD CROPS. . . . . . . . 3-2 3.7 MILK . . . . . . . . . . . . . . . . . . . . . . . 3-3 .

3.8 AMBIENT RADIATION MEASUREMENTS . . . . . . . . . . 3-3 3.9 QUALITY CONTROL. . . . . . . . . . . . . . . . . . 3-3 3.10 REFERENCES FOR ANALYTICAL PROCEDURES . . . . . . . 3-4

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i TROJAN NUCLEAR PLANT OPERATIONAL ENVIRONMENTAL RADIOLOGICAL ,

SURVEILLANCE PROCRAM CONTENTS Section Title Page 4.0 RESULTS AND DISCUSSION . . . . . . . . . . . . . . 4-1 4.1 SAMPLES FROM THE TERRESTRIAL ENVIRONMENT . . . . . 4-1 4.1.1 Air Particulates and Airborne I-131. . . . . . . 4-1 4.1.2 Food Crops . . . . . . . . . . . . . . . . . . . 4-1 4.1.3 Well Water . . . . . . . . . . . . . . . . . . . 4-2 l

4.1.4 Milk . . . . . . . . . . . . . . . . . . . . . . 4-2 4.1.5 Ambient Radiation Levels . . . . . . . . . . . . 4-2 4.2 SAMPLES FROM THE AQUATIC ENVIRONMENT . . . . . . . 4-3 4.2.1 Drinking Water Samples . . . . . . . . . . . . . 4-3 4.2.2 Shoreline Soil . . . . . . . . . . . . . . . . . 4-4 4.2.3 Fish . . . . . . . . . . . . . . . . . . . . . . 4-4 4.3

SUMMARY

OF RESULTS . . . . . . . . . . . . . . . . 4-4

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5.0 COMMENTS ON AND TERMS USED IN DATA TABLES. . . . . 5-1 i

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OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM TABLES Number Title 2-1 Sampling Locations and Frequency by Type 2-2 1987 Land Use Census 3-1 Program Analyses and Reported Detection Levels 3-2 1987 U. S. Environmental Protection Agency - Analysis Laboratory Intercomparison Program 3-3 1987 Quality Control Analyses Summary 4-1 Average Gross Beta Concentrations for Air Particulates 4-2 Radiological Environn .ual Monitoring Program Summary 5-1 Airborne Iodine-131 and Gross Beta in Air Particulate Filters (Weekly Collections) 5-2 Summary - Gross Beta in Air Samples 5-3 Gamma tmitters Concentrations in Air Particulates Filters 5-4 Radioactivity in Food Crops 5-5 Radioactivity in Well Water 5-6 Radioactivity in Milk 5-7 Ambient Gamma Radiation Levels for 1987 5-8 Radioactivity in Drinking Water 5-9 Radioactivity in Shoreline Soil 5-10 Radioactivity in Fish / Invertebrates FIGURES Number Title 2-1 Sampling Locations - December 31, 1987 2-2 Sampling Locations (Detail) - December 31, 1987 ill

ABSTRACT This report presents the data obtained through the analyses of environ-mental samples collected through the Portland General Electric Trojan Nuclear Plant Environmental Radiological Surveillance Program for the period January 1, 1987 through December 31, 1987.

In several milk samples, levels of radioactivity observed during 1987 were higher than years prior to 1986. This higher level of radio-activity was due to biota uptake of fallout radioactivity dispersed over Oregon from the April 1986 accident at the Chernobyl Nuclear Power Station in the Ukraine, USSR. In no case did radioactivity attributed to the Trojan Nuclear Plant exceed the Reporting Levels of the Trojan Radiolsgical Technical Specifications.

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1.0 INTRODUCTION

The Trojan Nuclear Plant, a 1130 megawatt-electric pressurized water reactor, first achieved criticality on December 15, 1975. This report presents the analytical data from the Environmental Radiological Surveillance Program with appropriate interpretation for 1987.

The analytical contractor during this period has been,TMA/Eberline, Albuquerque, New Mexico. In comparing data obtained during this period with those from previous periods, care should be taken to ensure that differences in procedures between the several contractors are considered. This is particularly true for "gross beta" measurements for j which the use of different reference nuclides may produce appropriately significant differences in gross beta concentrations.  ;

Information concerning the Environmental Radiological Surveillance Program prior to this period may be found in earli reports.

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4 2.0 SAMPLING ann PROGRAM PROCEDURES 2.1 SAMPLING LOCATIONS Sixty-seven (67) sampling locations were used in the Environmental Radiological Surveillance Program in 1987, 66 on land, and 1 in the Columbia River. This is the same number of sampling locations in use at the end of 1986.

The sampling locations are shown in Figures 2-1 and 2-2. Table 2-1 includes a listing of the sites, their distance from Trojan, and the type and frequency of sample collection.

2.2 SAMPLING PROCEDURES 2.2.1 AIR PARTICULATE AND RADIOIODINE Air particulate ar.d radioiodine sampling was performed weekly. The samples were gathered with a low-volume air sampling device which is I l

designed to draw a constant flow rate regardless of the pressure drop l across the filter. The sampling devices were set to maintain 1 cfm. The sample pump, metering devices, and timer were in a weatherproof housing.

The filter and cartridge were located in an inlet parallel to and about 1 meter above the tround. Glass fiber filters were used to collect particulate matter. Activated charcoal cartridges were used to collect radiolodine.

The glass fiber filter was removed from the air sampler and placed in a 2-inch plastic petri dish. The activated charcoal cartridge was removed at the same time. Air flow readings and other data required to compute the levels of radioactivity were recorded and submitted to the analysis laboratory along with the samples.

i 2-1

2.2.2 AMBIENT RADIATION MEASUREMENTS USING TLDs Thermoluminescent dosimeters (TLDs) were placed for field exposure and collected on a quarterly frequency. The TLDs were placed about 1 meter above ground level in plastic bags. The time of collection, the exposure period, and any abnormal conditions such as moisture in the holders, damage done by animals, etc. were recorded when the TLDs were retrieved.

Care wss taken to minimize exposure to the TLDs between collection and delivery to the laboratory. The TLDs were transported to the field in lead boxes to ensure low background levels. Control TLDs were carried with the field TLDs during collection and delivery.

2.2.3 FOOD CROPS Representative samples of tuberous and foliar fruits and vegetables were collected during local harvesting. Samples of leafy vegetables were collected during each of the three summer months of June, July, and August. Samples were sealed in plastic bags following collection, taking care not to include any soil or foreign material. The sample site identification number, the date collected, the sample type, and the amount obtained were recorded on the data collection forms.

2.2.4 MILX Milk samples (cow or goat) were collected monthly during January, February, and December with twice monthly collections during the other months. Milk was collected in polyethylene bottles (2 gallons for cow dairy and 1 gallon for goat dairy). Pelor to shipment of samples to the analysis laboratory, an ion exchange resin was used to concentrate any lodine present to improve datection sensitivity. The whole milk (after iodine removal) and resins were labeled and collection data forms prepared specifying sample site, date collected, sample type, and volume obtained.

2-2

2.2.5 WELL WATER Well water was collected quarterly either from the tap that leads off the pump or directly from the well itself. At sites with faucets the line was purged for 1 minute prior to collection. Sixty milligrams were drawn from the 1-gallon sample for tritium analysis. The remainder of the sample was put in a 1-gallon polyethylene bottle and acidified with concentrated hcl. The bottles were securely sealed, labeled, and collection data forms prepared specifying site, date collected, volume, and sample type.

2.2.6 DRINKING WATER Monthly composite samples of municipal drinking water wcce collected for Rainier (Sample Location 2) and St. Helens (Sample Location 66) at their respective intake structures on the Columbia River. Rainier is downstream of the Trojan Nuclear Plant while St.*Helens is upstream. At each location, a compositing sampler took a sample every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and aliquots of this monthly composite were sent for analysis. From these aliquots, 60 milliliters are sent for tritium analysis and a 1-gallon polyethylene bottle is acidified with concentrated hcl and sent for the l

other analyses. The bottles were securely sealed, labeled, and j collection data forms prepared specifying site, date collected, volume, and sample type.

2.2.7 SHORELINE SOIL Shoreline soil samples of about 1 quart in volume were taken twice a year. The samples were taken from a 1 square foot area with the vegetation and large rocks removed before sample collection. The soil sampling depth varied between 1 to 4 inches and the soll was passed through a No. 6 sieve before placement in the plastic collection i

bottles. The sample site identification number, date collected, and l volumo obtained were recorded on the collection data forms.

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1 2.2.8 A00ATIC ANIMAL i Aquatic animal sampling was performed semiannually. Both indigenous and anadromous species of fish and invertebrates such as crayfish were acquired by scining, netting, or trapping. The radioactivity analysis was performed on fish muscle or crayfish muscle samples. If needed for a pk 'icular sampling location, the fish muscle sample may be a mixture of several panfish species. The sample site identification number, the date collected, the fish species, and the amount obtained were recorded on collection data forms.

2.3 YEARLY LAND USE CENSUS WITHIN 5-MILE RADIUS OF TROJAN The annual land use census within a 5-mile radius of Trojan Nuclear Plant was performed during August 1987. Identified by this census were the locations of the nearest milk animal (cow and goat), meat animal, residence, and vegetable garden in each of the 16 meteorological sectors within this area. This census was completed by driving the roads within ,

a 5-mile radius of Trojan. Table 2-2 presents the results of the yearly land use census.

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TABLE 2-1 Sheet 1 cf 6 ,

SAMPLING LOCATIONS AND FREQUENCY BY TYPE Terrestrial Aquatic Radial Air Air Well Surf Shore Sample Location Mileage' Direction Partic' I-131' TLD Ven Milk' Water Water Soll Anim ONSITE 1A - U. S. 30 & E-W Road 0.8 NW Q S/A to Prescott IB - U. S. 30 W of 0.5 WSW Q Containment 1C - Cemetery on hill 0.7 SW Q W of Plant ID - Recreation Lake 0.7 S S/A lE - S site boundary. 0.8 S Q U. S. 30 at Railroad (RR)

IF - Meteorology tower 0.5 S W W Q 1G - S of Containment 0.1 SSE Q 1H - Plant cooling tower 0.2 ESE Q II - N site boundary at 0.5 NNW W W Q HT Columbia River 1J - RR & E-W road to 0.6 NNW Q Prescott 20 - S of Plant on 0.4 SSE Q Columbia River shore NOTE: Legend at bottom of Page 6 of 6 of Table 2-1.

TABLE 2-1 Sheet 2 of 6 Terrestrial Actuatic Radial Air Air Well Surf Shore Sample Location Mileage' Direction Partic'I-131 TLD VeK Mill- Water Water Soil ' Anim ONSITE 21 - SE cf Plant on 0.3 SE Q Columbia River shore l 22 - Between Recreation O.4 SSW ')

Lake and U. S. 30 l

23 - U. S. 30 S of E-W 0.6 WW Q road to Prescott 24 - Recreation Lake near 0.5 WSW Q E-W road to Plant 64 - W corner of 0.5 W Q Reflection Lake OREGON 2 - Rainier 3.8 NW W W Q MC l

3 - LindberE (Kelly Res.) 2.0 NNW Q Q 4c - Prescott (Jack Falls 1.6 NW Q residential area) 6B - Coble (Neer Res.) 1.2 S W W Q Q 17A - Beaver Homes (Kandle 2.6 SSW SM

! Dalry) 19 - Portland 37.5 S W W SM 1 - - - _ _ _ _ _ _ - - _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - - - _ - _ - - - _ _ _ _ _ . --__-_-_--_ _ -

TABLE 2-1 Sheet 3 cf 6 ,

Terrestrial Avluatic Radial Air Air Well Surf Shore Sample Location Mileage Direction Partic I-131 TLD Veg Milk Water Water Soll ' Anim l

ORECON 25 - Prescott (Shoreline) 0.6 N Q 26 - Deer Island (Tide 5.0 S Q Creek) 27 - Colushia City (Gensman 9.6 S Q Road) 28 - Shiloh Basin (Orr 4.7 SSW Q Road) 29 - Trenholm (Canaan 10.7 SSW Q Road) 30 - Shiloh Basin 5.0 SW Q (Whitney Road) 31 - Aplary (Schaffer Road) *0.1 SW Q 32 - Fern Hill (Lentz 5.2 WSW Q Road) 33 - Aplary (Van Natta Road) 8.6 WSW Q 34 - Fern Hill (Lentz 5.0 W Q Road) 35 - Swedetown (Swedetown 10.0 W Q Road) 36 - Rainier (Doan Road) 5.2 WNW Q

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TABLE 2-1 Sheet 4 of 6 Terrestrial Aquatic Radial Air Air Well Surf Shore Sample Location Mileage Direction Partic I-131 TLD Vet Milk Water Water Soll Anim ORECON 37 - Delena (Lost Creek 10.0 WNW Q Road)

I 38 - Rainier (Highway 30) 4.8 NW Q i l

39 - Alston-Mayger Road 9.9 NW Q l l

56 - Deer Island 3.2 SSE Q 63 - Rinck Dairy 8.1 WWW SM 66 - St. Helens (Municipal 10.5 SSE MC Water Supply) 68 - Winans Dairy 5.0 SW SM WASHINGTON 11A - Kalama River 0.8 SE Q (Columbia River) 118 - Kalama River 1.4 ENE W W (Public Utility District Substation) 14 - Longview (Ocean 8.2 NNW W W Beach substation) 40 - Longview (RR) 5.8 NNW Q 41 - Eufaula 10.7 NNW Q 42 - Kelso (near Hwy 4) 6.6 N Q

TABLE 2-1 Sheet 5 cf G Terrestrial Aquatic Radial Air Air Well Surf Shore

'2mple Location Mileage' Direction Partic I-131 TLD Veg Milk Water Water Soll Anim WASHINGTON 43 - LexinE ton 10.3 N Q 44 - Kelso (N Maple Hill 5.2 NME Q Road) 45 - Mt. Brynlon 9.1 NNE Q 46 - Rose Valley 5.3 NE Q 47 - Smith Mountain 9.2 NE Q 48 - Mt. Pleasant 5.6 ENE Q 49 - Coble Mountain 7.8 ENE Q 50 - Kalama River 5.0 E Q (Fallert Road) 51 - Kalama River 10.0 E Q (Kalama River Road) 52 - Kalama (China Carden 5.2 ESE Q Road) 53 - Ross Peak 10.7 ESE Q 54 - Cloverdale 5.2 SE Q 55 - Woodland (Green 10.0 SE Q Mountain Road) 57 - Woodland (Dike Road) 9.5 SSE Q

TABLE 2-1 Sheet 6 of 6 Terrestrial I A<luatic Radial Air Air Well Surf Shore Sample Location Mileage' Direction Partic' I-131 TLD Veg ' Milk Water' Water' Soll 'Anim WASHINGTON 58 - Kalama (N of Port of 1.6 SE Q Kalama Marina) 59 - Kalama (S of Sports- 1.5 ESE Q man Road) 60 - Kalama (N of 1.2 ENE Q Sportsman Road) 61 - Carrolls (W Kingsbury 1.5 NE I Q

Road) 62 - W of Carrolls Channel 1.0 NNE Q COLUMBIA RIVER CR3 - Trojan 72.4* E S/A S/A I

LEGEND:

W - Weekly.

Q - Quarterly.

SM - Semimonthly except monthly during December, January, and February.

MC - Monthly composite, semimonthly composite if I-131 analysis required.

4 S/A - Sealannually.

HT - Harvest time.

  • - Columbia River mileage refers to river miles (measured from mouthl.

TABLE 2-2 1987 LAND USE (~ENSUS NEAREST LOCATION TO TROJAN WITHIN A FIVE-MILE RADIUS Radiation Mileage for Nearest Location Directional Meat Sector Residence Carden Milk Cow Milk Goat Animal N 0.6 0.6 None None None NNE 2.4 2.4 None 3.0 2.7 NE 1.6 1.8 None None 1.8 ENE 2.4 2.4 None None 5.0 E 1.3 1.6 None None 1.4 ESE 0.8 1.8 None None 1.7 SE 2.5 2.5 None None 2.5 SSE 1.4 1.4 None None 3.0 S 1.2 1.4 None None 2.0 SSW 0.9 0.9 None 2.6 1.0 4

SW 1.5 1.5 None None 1.6 WSW 1.4 1.9 None None 1.9 W 1.7 2.1 None None 1.7 WNW 1.7 1.7 None None 1.8 j 1.2 NW 1.2 None None 1.2 NNW 0.6 J.? None None 2.0 t

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un me aai" " Figure 2-2. SAMPLING LOCATIONS (Detail) 1 I

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3 I I I I

3.0 ANALYTICAL PRCCEDURES AND COUNTING METHODS Samples are analyzed for the various radioactive components by standard radiochemical methods. These methods are equal to, and in most cases, identical with, those of the U. S. Department of Energy (Health and ,

Safety Laboratory (HASL) Procedures Manual, RASL-300, see references, Section 3.10), or those of the U. S. Environmental Protection Agency (EPA).

Analyses of individual sample types, general methods, and routine ana-lytical sensitivities are discussed below. The analytical program and sensitivity requirements are given in Table 3-1, 3.1 ANALYTICAL DETECTION LIMITS AND COUNT RATE ERRORS In environmental radiological analyses the dominant known uncertainty is usually the sample count rate. Error terms given in this report are based on this factor since all other analytical uncertainties are

relatively small. Uncertainties are calculated by standard methods (MASL-300), and are reported at the 95-percent confidence level (2o).

The lower limit of detection (LLD) is defined as the smallest concentra-tion of radioactive material in a sample or the smallest amount of radia-tion to a dosimeter that will yield a not indication, above system background, that will be detected with 95-percent probability with only 5-percent probability of falsely concluding that a blank observation represents a real signal. Analytical data for samples for which concen-trations are less than or equal to.the LLD are preceded by the symbol "<".

3.2 AIR PARTICULATES Gross beta concentrations are measured with low background, window-type (0.85 mg/cm in thickness), proportional counting systems. The routine detection limit (LLD) is 0.002 pC1/m for gross beta measurements assuming a collected air volume of 300 m / week.

i 3-1 i

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Gamma isotopic analyses are performed with germanium detectors with a 1 3

routine detection limit of 0.05 pCi/m for the gamma emitters. <

3.3 RADIOIODINE The charcoal cartridges used are of the TEDA-impregnated type. The iodine is extracted from the charcoal, chemically separated, and counted as AgI using the low-background beta counters mentioned in Section 3.2 which yield an LLD of 0.05 pci/m .

3.4 DRINKING AND WELL WATER Gross beta analysis of water samples is performed by evaporation of a measured aliquot of the sample, digestion, planchetting of the processed sample and radiometric assay by the low-background beta counters men-tioned in Section 3.2, with an LLD of 0.5 pC1/1. Tritium analysis is performed on all water samples to the required LLD of 1000 pCL/1 by liquid scintillation counting. Gamma isotopic analysis is performed using germanium detectors with a routine LLD of 10 pCi/1 per gamma emitting radionuclide.

3.5 SHORELINE SOIL Samples are oven-dried and results reported based on dry weight. Camma emitters are measured with germanium detectors with an LLD of 0.1 pCi/g per nuclide.

3.6 FISH. INVERTEBRATES. AND FOOD CROPS Measured amounts of these types of samples are analyzed for gamma emitters by gamma spectrometry with counting times adjusted to provide LLDs at least as sensitive as those required in Table 3-1 for the  !

I appropriate sample type.

3-2 l

3.7 MILK The determination of Iodine-131 in fresh milk is based on anion exchange removal of the Iodine-l'31 followed by radiochemical purification and low background beta counting using the systems described in Section 3.2.

The LLD is 0.5 pCi/1 or better. Gamma emitters in milk are measured with germanium detectors with an LLD of 10 pC1/1 per nuclide. The analysis for Strontium-89 and Strontium-90 is performed on ashed samples using a strontium chemical yield and two-separation technique with an LLD of 1.0 pCi/1.

3.8 AMBIENT RADIATION MEASUREMENTS The respons'ibility for ambient radiation dose measurements resides with Portland General Electric Company (PCE). A total of 57 field locations were monitored with the dosimeters analyzed quarterly. The field dosimeters used thermoluminescent radiation detection materials (CaF :Dy, 2

TLD-200 chips) with each dosimeter having more than two separate chips or measurement devices. For each field dosimeter, the chips were packed in a plascic ferm and sealed in shielded containers. To minimize radiation energy dependence for the TLD-200 chips, the field dosimeters were shielded with a two-element filter cf 10 mil tantalum and 2 mil lead as described in the report by Denham, et al (see Section 3.10).  ;

Calibration of the field dosimeters was performed with a Cesium-137  !

l source traceable to the U. S. National Bureau of Standards. Calibration dosimeters were prepared for each readout of the field dosimeters.

3.9 OUALITY C0KTROL Approximately 15 percent of the analyses performed by the analysis laboratory are for quality control purposes. The analysis laboratory participates in EPA, Nuclear Regulatory Commission, and other intercalibration programs. Reports of all quality control analyses j 3-3

are presented monthly to PGE. Results of EPA intercalibrations (for which "known" data are available) are given in Table 3-2. In those cases where discrepant values are obtained, the analysis laboratory performs an investigation to determine the cause and corrective action as required.

Table 3-3 summarizes the intralaboratory quality control results for the year 1987.

During 1981, 1982, and 1984 PCE participated in the Fifth, Sixth, and Seventh International Intercomparison of Envirot mental Dosimeters. The results of these participations were presented in the 1982, 1983, and 1984 reports, respectively. By the successful PCE participation in these three intercomparison projects, the measurement method for the environ-mental ambient radiation levels has been shown to be appropriate and accurate.

R 3,10 REFERENCES FOR ANALYTICAL PROCEDURCS

1. American Public Health Association. American Water Work 2 Association and Water Pollution Control Federation (1971): Standard Methods for the Examination of Water and Wastewater. Thirteenth edition, pp 583-632; 12th edition, pp 325-352. APHA, 1740 Broadway, New York, NY 10019,
2. Department of Health, Education and Welf are, Public Health Service:

Radioassay Procedures for Environmental Samples. National Center for Radiological Health (1967), Sec. 1, pp 36-115,

3. Atomic Energy Commission: Regulatory Culde 4.3 (September 1973).

4 Health and Safety Laboratory Atomic Energy Commission: NASL Procedures Manual (now known as EML of the Department of Energy).

HASL, 376 Hudson Street, New York, NY 10014.

5. National Envirorrf_nts! Research Center, Environmental Protection "

Agency; Handbook of Radiochemical Analytical Methods. Program Element 1HA 325. Office of Research and Development, Las Vegas, NV 89114.

6. D. H. Denham, R. L. Kathren, and J. P. Corley, "A Ca2:D/

Thermoluminescent Dosimeter for Environmental Monitorina". USAEC Report ENWL-SA-4191 (1972).

3-4

TABLE 3-1 PROGRAM ANALYSES AND REPORTED DETECTION LEVELS Proaram Analysis Reported Detection Limits (LLD)l3I Air Particulate-gross beta 0.002 pCL/m 3 Air Particulate-gamma scan 0.05 pC1/m3 /nucilde Air Radiolodine 0.05 pCi/m 3 Food crops-garna scan 0.02 pCi/g/nuclide (wet)

Milk-Iodine-131 0.5 pCi/ liter Milk-Strontium 89/90 1.0 pCi/ liter Milk-gamma scan 10 pCi/ liter /nuclide Water-gross beta 0.5 pCi/ liter Water-tritium 1000 pCL/ liter Water-gamma scan 10 pCi/ liter /nuclide Shoreline Soil-gamma scan 0.1 pCi/g/nuclide (dry)

Fish / Invertebrates-gamma scan 0.1 pC1/g/nuclide (wet)

Direct Radiation 0.04 mR/ day (a) Reported detection level or I.LD is defined in Section 3.1.

l l

TABLE 3-2 Sheet 1 of 2 1987 U. S. ENVIRONMENTAL PROTECTION ACENCY (EPA)

ANALYSIS LABORATORY INTERCOMPARISON PROCRAM Eberline  :

Sample Type Analysis EPA Value Value Units Wa te;- Alpha 11.015.0 12.312.7 pCi/1 pCi/1 4 Water Ra-226 6.8011.02 5.2712.21 Water Ra-228 11.1011.67 6.2712.20 pCi/1 Water Beta 10.015.0 13.012.9 pCi/1 Water Pu-239 16.7011.67 17.4010.70 pC1/3 Water H-3 42091421 46331570 pC1/1 Water Sr-90 25.015.0 22.013.7 pCi/1 Water Sr-90 25.011.5 26.312.7 pCi/1 Water U(Nat.) 8.016.0 11.711.7 pC1/1 Water Alpha 3.015.0 2.710.6 pCi/1 Water Beta 13.015.0 9.311.2 pCi/1 Water Ra-226 7.3011.10 5.9710.71 pCi/1 Water Ra-228 7.5011.13 9.1012.35 pC1/1 Water H-3 56201562 61301156 pCi/1 Water H-3 28951357 34171310 pCi/1 Water Alpha 30.018.0 35.712.0 pCi/1 Water Beta 66.015.0 75.314.0 pCi/1 ,

Water Sr-89 19.015.0 15.714.0 pCi/1 Water Sr-90 10.011.5 10.712.3 pCi/1 Water co-60 8.015.0 5.611.8 pCi/1 Water Cs-134 20.015.0 11.911.3 pCi/l Water Cs-137 1515.0 10.511.5 pCi/1 Water Ra-226 3.9010.60 3.9010.17 pC1/1 Water Ra-228 4.0010.60 5.5011.0 pCi/1 Water U(Nat.) 5.0016.00 5.6710.80 pCi/1 .

Water Alpha 5.015.0 4.010.8 pCi/1 Water Beta 5.015.0 3.310.6 pCi/1 '

Water Sr-89 41.015.0 42.015.9 pC1/1 Water Sr-90 20.011.5 27.317.1 pCi/1 i Water Cr-51 41.015.0 30.7112.0 pCi/1 l Water Co-60 64.015.0 57.713.2 pci/1 i Water 2n-65 10.015.0 4.6612.00 pCi/1 Water Ru-106 75.015.0 62.7113.0 pCi/1 Water Cs-134 40.015.0 30.012.0 pCi/1 Water Cs-137 80.015.0 68.312.1 pCi/1 Water Ra-226 7.3011.30 6.3010.30 pCi/1 Water Ra-228 15.2012.28 12.612.00 pci/1 Water Alpha 4.015.0 5.011.9 pCi/1 Water Beta 12.015.0 12.012.3 pC1/1 i W:ater I-131 48.016.0 52.012.6 pci/1 Water Pu-239 5,3010.53 5.5310.47 pC1/1 Water U(Nat.) 13.016.0 14.710.7 pCi/1 Water H-3 44921449 36201297 pCi/1 Water Ra-226 9.7011.46 9.6010.26 pCi/1 Water Ra-228 6.3010.95 10.1710.25 pci/1 i

)

TABLE 3-2 Sheet 2 of 2 Eberline Sample Type Analysis EPA Value Value Units Air Falter Alpha 14.015.0 14.712.5 pCi/ sample Air Filter Beta 43.015.0 47.011.3 pCi/saiaple Air Filter Cs-137 8.015.0 13.011.8 pCi/ sample Air Filter Alpha 1015 9.6710.58 pci/ sample Air Filter Beta 3015 3211.7 pC1/ sample Air Filter Sr-90 1011.5 8.3310.58 pCi/ sample Air Filter Cs-137 1015 20.711.5 pC1/ sample Milk I-131 9.0010.90 7.6711.0 pC1/1 Urine H-3 52571526 49871180 pC1/1 Urine H-3 74321743 60271133 pCi/1

-d

o TABLE 3-3 Sheet 1 of 2 1987 QUALITY CONTROL ANALYSES

SUMMARY

The table below summarizes results of samples run for process quality control purposes during the subject year. These listings are in addition to such measurements as detector backgrounds, check source values, radiometric-gravimetric comparisons, system calibrations, etc. Detailed listings of each measurement are maintained at the analysis laboratory ,

and are available for inspection if required.

Blank Samples ,

Nuclide Number of Number of Analyses Exceeding Analyzed Determinations the LLD for that Analysis Gross Alpha 69 0 Cross Beta 36 0 H-3 30 0 U-234 45 0 l U-238 15 0 Th-230 124 0 Ra-226 90 0 1 Ra-228 7 0 i Pb-210 4 0 Sr-89 20 0 Sr-90 48 0 Pu-239 25 0 Am-241 19 0 I-131 5 0

Fe-55 3 0 Spiked Samples Nuclide Number of Within 2 Sigma Within 3 Sigma Analyzed De t e ms . of Kn own of Known Cross Alpha 69 69 -

Gross Beta 36 36 -

H-3 30 30 -

U-234 45 45 -

1 U-238 15 15 -

Th-230 124 124 -

Ra-226 90 90 -

Ra-228 7 7 -

Pb-210 4 4 -

Sr-89 20 20 -

Sr-90 45 45 -

Pu-239 25 25 -

Am-241 19 19 -

I-131 5 5 -

Fe-55 3 3 -

l TABLE 3-3 Sheet 2 of 2 i I

i Sollt Samples i

j Nuclide Number of Within 2 Sigma Within 3 Sigma

, Analyzed Determs. of Known of Known Gross Alpha 57 57 -

l

(

Gross Beta 37 37 -

H-3 29 29 -

U-234 46 46 -

U-238 11 11 -

Th-230 119 116 3 Ra-226 81 81 - [

Ra-228 7 7 -

Sr-89 16 16 -

l Sr-90 36 36 -

Pu-239 18 18 -

. Pb-210 1 1 -

. AM-241 15 15 -

FE-55 5 5 -

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4 4.0 RESULTS AND DISCUSSION 4.1 SAMPLES FROM Tile TERRESTRIAL ENVIRONMENT  !

4.1.1 AIR PARTICULATES AND AIRBORNE I-131 The gross beta air particulate data obtained during 1987 were comparable to the data obtained during the years of 1982, 1983, 1984, 1985, 1986 ,

(except May 1986), and the preoperationgl period. Gross beta concentrations for air particulates for all sampling periods in 1987 remained generally at low levels.

Average concentrations with their average standard deviations for the years 1987 and before are presented in Table 4-1 for both onsite and offsite locations. In October 1980, the Peoples' Repubile of China tested a nuclear device in the atmosphere. For this reason, the increased average concentrations in 1981 were due to increased fallout levels fecm the October 1980 Chinese test and not from operation of the Trojan Nuclear Plant. The larger average standard deviation for the 1986 '

data was due to the increased gross beta activity for May 1986 resulting from the Chernobyl incident.

Airborne I-131 concentration values for 19'87 were below the detuction limit of 0.0S pCi/m3 (at collection time) for all samples.

For 1987, the measurement of gamma emitting radionuclidas in quarterly composites of air particulate filters for each monitoring location did '

not show detectable activity above the detection limit of 0.05 pCi/m3 .

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Data for these air monitoring samples are listed in Chapter 5,  ;

Tables 5-1, 5-2, and S-3. l I

1 4.1.2 FOOD CROPS Samples of food crops (garden produce) were collected and analyzed for i

gamma emitters. The sample collections of these garden produce were made l {

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during the harvest months of June. July, and August 1987. Camma emitting radionuclides were not detected in the food crop samples. The data are

~

presented in Chapter 5. Table 5-4.

4.1.3 WELL WATER Well water samples were collected quarterly from three locations.

Tritium and samma emitting radionuclide levels were below the sensicivity requirements of the program. The data are presented in Chapter 5 Table 5-5.

4.1.4 MILK Milk samples were collected from four locations and were analyzed for I-131. Sr-89 Sr-90, and and gamma emitters. No samples contained I-131 or Sr-89 at detectable levels. Most samples contained Sr-90, which is attributable to worldwide f allout due to atmospheric weapons tests.

l During the months March through June and in December,17 of 88 milk samples collected for the year showed detectable levels of radiocesiums.

Five of these samples exceeded 20 pCi/1. The lack of I-131 and Se-89 radioactivity in the milk samples shows that the measured cesium radioactivity is attributable to fallout radioactivity due to the April 1986 Chernobyl incident in Russia, rather than operational activity of the Trojan Nuclear Plant. Refer to the 1986 report for discussion of this incident.

The milk sample data are presented in Chapter 5. Table 5-6.

4.1.5 AMBIENT RADIATION LEVELS Ambient dose rates in mR/ day for dosimeters at measurement locations in the environs around the Trojan Nuclear Plant are shown in Chapter 5 Table 5-7. Several of these measurement locations were established before the Plant became operational. The mean and standard deviation 4-2 l

for the quarterly dosimeters data has been calculated for the three geo-graphical groups of Oregon, Washington, and Trojan onsite locations.

For 1987, the mean ambient dose rates were: 0.1310.03 mR/ day for the 14 Trojan onsite locations, 0.1510.03 mR/ day for the 20 Oregon locations, and 0.1210.02 mR/ day for the 23 Washington locations. These values do not differ significantly from the results of previous years.

Another manner for review of the ambient radiation measurements is to divide the results between three rings which are grouped as to radial distance from Trojan: the close ring (24 locations) at distances from 0.1 to 2.0 miles; the 5-mile ring (17 locations) at distancen from 2.1 to 7.0 miles; the 10-mile ring (16 locations) at distances from 7.1 to 10.7 miles. The 10-mile ring serves as the control locations for the ambient radiation measurements. Each ring has at least one measurement location in each of the 16 directional sectors. The measurement mean and standard deviations were calculated to be 0.1310.03 mR/ day for all locations, with the close, 5-mile, and 10-mile rings being 0.1210.03 mR/ day, 0.1410.03 mR/ day, and 0.1410.03 m'Jday, respectively. These data indicate that the operational rativities of the Trojan Nuclear plant do not affect the anblent radiaLion levels around the Plant.

The ambient gamma radiation data in Table 5-7 were also analyzed for dose rate differences in the four major compass directions from the Trojan Nuclear Plant. No significant differences were found, in respect to both the compass directions or the similar data from 1986 and before. The values were: 0.1310.03 mR/ day for the 16 north locations.

0.1110.02 mR/ day for the 9 east locations. 0.1510.04 mR/ day for the 12 south locations, and 0.15 0.03 mP/ day fo? the 6 west locations.

4.2 SAMPLES FROM ThE AOUATIC EMVIRONMENT 4.2.1 DRINKING WATER SAMPLES composited drinking tster samples were collected from municipal water supply locations on the Columbia River that are downstream (Sample 4-3

)

  • i Location 2) and upstream (Sample Location 66) of the Trojan site.

The samples were analyzed monthly for gross beta activity, tritium, and gamma emitters. The data are presented in Chapter 5, Table 5-8.

No radioactivity attributable to operation of the Trojan Nuclear Plant was detected in any of the water samples. ,

4.2.2 SHORELINE SOIL Shoreline soll samples were collected from a location on the bank of the Columbia River near the Trojan site. Analyses were performed for skmma emitters. The data are presented in Chapter 5. Table 5-9. None of the shoreline soil samples showed detectable levels of gamma emitters.

4.2.3 FISH Fish and crayfish were collected twice during the year and the fillets and/or tails were analyzed for gamma emitters. None of the fish or l

crayfish sa=ples contained gamma emitting radionuclides larger than the detectability level of 0.1 pCL/s. The data are presented in Chapter 5 Table 5-10.

I 4.3

SUMMARY

OF RESULT 3  !

l Table 4-2 presents a summary of the radioactivity analysis results for each medium or pathway sampled for the 1987 Radiological Environmental Monitoring Program around the Trojan Nuclear Plant. The format of Table 4-2 is that which is required by Trojan Technical Specification 6.9.1.5.2.

i A review of Table 4-2 shows that, except for milk, none of the radio activity measurements were larger than the Reporting Levels defined by I

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1 Technical Specification 3.12.1. The milk samples that exceeded the f Reporting Levels were determined to be caused by fallout radioactivity and not Trojan Plant operations, j j

For the gross beta analyses of the air particulate samples, the value for the location with the highest annual mean was not significantly different from the the values for the control location or all locations. l For the milk samples, the only detectable radioactivity was due to the atmospheric weapons testing and the Chernobyl nuclear accident f allout radionuclides, Sr-90, Cs-134, and Cs-137. Also, the dairy with the highest measured values of Sr-90, Cs-134, and Cs-137 was a goat dairy.

G)ats tend to concentrate radioactivity in the milk to a greater degree than do cows.

For the ambient radiation measurements, the mean value for the control locations (10-mile ring) was not significantly different than the mean  ;

values for all locations or the close ring (see section 4.1.5). l l

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For the radioactivity measurements in drinking water, the annual mean for the gross beta determination was higher for the upstream (Columbia River)

, or control location (St. Helens) than it was for the downstream location

. (Rainier).

1 As is shown by Table 4-2, except for allk, most of the radioactivity 1 me;asurements performed for the 1987 Trojan Nuclear Plant Radiological Environmental Monitoring Program were at or below the level of detect-j ability. There is no indication that the operations of the Trojan

! Nuclear Plant had a radiological impact on the environs around the Plant.

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6 TABLE 4-1 j i

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' AVERACE GROSS BETA CONCENTRATIONS i FOR AIR PARTICULATES l i

i (Units: 10"* DCl/m*)

t Trojan Oregon Washington (onsite) (offsite) Joffsite)

Preop 212 212 3+2 l 1976 216 318 214 1977 314 414 512 1978 212 211 211  !

1 1979 111 til 111  ;

l j 1980 314 314 214 1981 1112 1114 1111 .

1982 215 2 17 2 16 j 1983 212 212 212 l 1984 212 212 2+2 i i 1985 212 211 211 i 1986 317 316 317 3 1987 til 111 111 l

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TABLE 4- 2 Sheet I cf"2 RADIOLOGICAL ENVIROINGENTAL MONITORING PROGRAM

SUMMARY

Trojan Nuclear Plant, Columbia County, Oregon. Docket 50-344. Reporting Period: January 1-December 31, 1987 Type and All Indicator Location.With Highest Annual Mean Control Locations Medium or Pethway Total Number Lower Limit Locations Name Number of Sampled (Unit of of Analyses of Detection Mean(f)I*I Distance and Mean(f)I*I Mean(f)(al Reportable Measurement) Performed (LLD) Range Direction htange Range Events Air Particulates Cross 8 0.002 0.014(364/364) 5 of the 6 samplo 0.014(260/260) 0.015(52/52) N/Albl (pC1/m3 ) 364 0.004-0.042 sites, see 0.004-0.042 0.003-0.034 j Table 5-2 l I-131 0.05 <LLD - <LLD <LLD 0 l

364 y-scan 0.05/nuc11de <LLD -

<LLD <LLD 0 l 28 Food crops y-scan 0.02/nuclide <LLD -

<LLD N/A 0 (pcl/g - wet) 8 Well Water Tritium 1000 <LLD -

<LLD N/A 0 (pci/ liter) 12 y-scan IO/nuclide <LLD -

<LLD N/A 0 12 cilk I-131 0.5 <LLD -

<LLD <LLD 0 (pC1/ Iller) 88 Sr-89 1.0 <LLD -

<LLD <LLD N/A{b]

88 Sr-90 1.0 3.0(68/88) 63-Rink Dairy 3.8(22/22) 1.6(10/22) N/A{b]

88 0.6-13.0 8.1 al - WWW 1.0-13.0 0.6-2.8

TABLE 4-2 Sheet 2 of 2 Type and All Indicator Location With Highest Annual Mean Control Locations Medium or Pathway Total Number Lower Limit Locations Name Number of Sampled (Unit of of Analyses of Detection Mean(f)[a] Distance and Mean(f)[a] Mean(f)[a] Reportable Measurement) Performed (LLD) Range Direction Range Range Events y-scan, 10/nuclide - - -

0 88 Cs-134 14(3/88) 63-Rink Dairy 14(3/22) <LLD 0 10-20 8.1 mi - WNW 10-20 Cs-137 21(17/88) 63-Rinck Dairy 28(9/22) 8.5(2/22) 0 8-40 8.1 mi - WNW 8-40 8-9 Ambient Radiation y-exposure 0.04 0.13(223/223) 1H-Plant Cooling 0.20(4/4) 0.14(63/63) N/A[b]

(mR/ day) 223 0.05-0.27 Tower 0.16-0.27 0.09-0.20 0.2 mi - ESE Drinking Water Cross 8 0.5 3.5(24/24) 66-St. Helens 3.8(12/12) 3.8(12/12) N/A[b]

(pC1/ liter) 24 1.7-6.9 (control) 2.2-5.6 2.2-5.6 10.5 mi - SSE Tritlum 1000 <LLD -

<LLD <LLD 0 24 y-scan 10/nuclide <LLD -

<LLD <LLD 0 24 Shoreline Soll y-scan 0.1/nuc11de <LLD -

<LLD N/A[b] N/A[bl (PCi/g - dry) 2 Fich/ Invertebrates y-scan 0.1/nuc11de <LLD -

<LLD <LLD 0 (pci/g - wet) 8

[o] Mean and range based upon detectable measurements only. The fraction of detectable measurements at specified locations is indicated in parentheses (f).

[b] N/A - Not applicable. .

l

! o 5.0 COMMENTS ON AND TERMS USED IN DATA TABLES Wet Weight A reporting unit used with organic tissue samples such as vegetation and aquatic animal samples in which the amount of sample is taken to be the weight as received from the field with no moisture removed.

Dry Weight A reporting unit used for shoreline soil in which the amount of sample is taken to be the weight of the sample after removal of moisture by drying in an oven at abcut 110'c for about 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />.

pCL/m A reporting unit used with air particulate and radio-iodine data which refers to the radioactivity content expressed in picoeuries of the volume of air expressed in cubic meters passed through the filter and/or the charcoal trap. Note that the volumes are not corrected to standard conditions.

Gama Emitters Samples were analyzed by high resolution germanium gama or spectrometry. The resulting spectrum is analyzed by a Gamma Isotopic computer program which scans about 50 to 2000 kev and lists the energy peaks of any nuclidec present in concentrations exeseding the sensitivity limits set for that particular experiment.

Error Tarms Figures following "t" are error terms based on counting uncertainties at the 2e (95-percent confidence) level. Values preceded by the "<" symbol were below the stated concentration at the 3o (99-percent confidence) level.

5-1

I l . e sensitivity All analyses meet the sensitivity requirements of the program as given in Table 3-1. For the few samples that do not (because of inadequate sample quantitles, analytical interference, etc), the sensitivity actually obtained in the analysis is given.

Comment When all analyses of a particular type during the period resulted in concentration 9 below the sensitivity limits, a statement is made on th. appecpriate table rather than presenting a whole page of "<" data. If all but one or two data points are below the sensitivity limits. the previously mentioned convention is followed and the finite data are given as footnotes.

5-2 l

1

4 TABLE 5-1 Sheet 1 of 7 AIRBORNE 10 DINE-131* AND GROSS BETA IN AIR PARTICULATE FILTERS (Weekly Collections)

L.ocation 1Fa Location II*

Collection . Volume Cross B Collection Volume Gross 8 Date 3 (m ) (DC1/m3 ) Date (m3 ) (pci/m 3) 01/06/87 285 0.00710.003 01/06/87 285 0.00710.003 01/13/87 235 0.02810.004 01/13/87 285 0.02810.003 01/20/87 285 0.01710.003 01/20/87 285 0.01410.003 01/27/87 285 0.02810.003 01/27/87 285 0.02710.003 02/03/87 285 0.01310.003 02/03/87 285 0.01010.003 02/10/87 280 0.03810.004 02/10/87 280 0.03510.004 02/17/87 290 0.02010.003 02/17/87 290 0.01410.003 02/24/87 285 0.01110 003 02/24/87 285 0.01310.003 03/03/87 285 0.01310 003 03/03/87 285 0.02110.003 03/10/87 285 0.01110 002 03/10/87 285 0.01310.002 0J/17/87 285 0.00510.003 03/17/87 280 0.00510.003 03/24/87 280 0.00610.003 03/24/87 265 0.00910.003 03/31/87 265 0.00810.003 03/31/87 100 0.04210.009 04/07/87 285 0.01410.003 04/07/87 280 0.02110.003 04/14/87 285 0.00910.003 04/14/87 285 0.00810.003 04/21/87 285 0.01210.003 04/21/87 285 0.01110.003 04/28/87 285 0.01810.003 04/28/87 285 0.00610.003 05/05/87 285 0.01310.003 05/05/87 285 0.01410.003 05/12/87 285 0.01710.003 05/12/87 285 0.01310.003 05/19/87 285 0.00610.003 05/19/87 285 0.01310.003 05/26/87 285 0.01110.003 05/26/87 285 0.01210.003 06/02/87 285 0.00510.003 06/02/87 285 0.00710.003 06/09/87 285 0.01410.003 06/09/87 285 0.00910.003 06/16/87 285 0.00610.003 06/16/87 290 0.00910.003 06/23/87 285 0.00410.003 06/23/87 285 0.00710.003 06/30/87 285 0.00910.003 06/30/87 280 0.00910.003 07/07/87 280 0.007t0.003 07/07/87 285 0.00710.003 07/14/87 290 0.00410 003 C//14/87 290 0.00610.003 07/21/87 285 0.007t0.003 07/21/87 285 0.008t0.003 07/28/87 285 0.01110.003 07/28'87 280 0.01010.003 08/04/87 285 0.01310.003 08/04/87 285 0.00710.003 08/11/87 285 0.01110.003 08/11/87 285 0.01110.003 08/18/87 290 0.00810.003 08/18/87 290 0.00410.003 08/25/87 285 0.00910.003 08/25/87 280 0.00710.003 09/01/87 285 0.01910.003 09/01/87 285 0.01610.003 09/08/87 285 0.01510.003 09/08/87 285 0.01610.003 09/15/87 290 0.01110 003 09/15/87 285 0.01310.003 09/22/87 290 0.017+0.003 09/22/87 290 0.017+0.003 i

o Iodine cartridge concentrations are <0.05 unless otherwise noted.

e TABLE 5-1 Sheet 2 of 7 AIRBORNE 10 DINE-131* AND GROSS BETA IN AIR PARTICULATE FILTERS (Weokly Collections)

Location 1F* Location II*

Collection Volume Gross O Collection Volume Cross B Date (m3 ) (oci/m 3) __ Date (m3 ) (oci/m 3) 09/29/87 280 0.01610.003 09/29/87 285 0.01610.003 10/06/87 285 0.02410.003 10/06/87 285 0.02210.003 10/13/87 280 0.02310.003 10/13/87 285 0.02810.003 10/20/87 290 0.01610.003 10/20/87 285 0.01810.003 10/27/87 285 0.02610.003 10/27/87 285 0.03010.003 11/03/87 285 0.02110.003 11/03/87 290 0.02510.003 11/10/87 285 0.02010.003 11/10/87 280 0.02110.003 11/17/87 285 0.01010.003 11/17/87 285 0.01210.003 11/24/87 285 0.01910.003 11/24/87 285 0.01810.003 12/01/87 285 0.01110.002 12/01/87 285 0.00910.002 12/08/87 285 0.00410.003 12/08/87 285 0.00510.003 12/15/87 285 0.01010.003 12/15/87 290 0.00910.003 12/22/87 285 0.02210.003 12/22/87 285 0.02110.003 12/29/87 280 0.02010.003 12/29/87 285 0.01910.003

  • Iodine cartridge concentrations are <0.05 unless otherwise noted. '

I 1

u

TABLE 5-1 Sheet 3 of 7 AIRBORNE IODINE-131* AND CROSS BETA IN AIR PARTICULATE FILTERS (Weekly Collections)

Location 68* Location 11B*

Collection Volume Gross S Collection Volume Gross 8 Date (m3 ) (DCi/m3 ) Date (m3 ) (DC1/m3 )

01/06/87 285 C.00710.003 ,

01/06/87 285 0.00010.003 01/13/87 285 0.02810.004 01/13/87 285 0.03010.004 01/20/87 285 0.01310.003 01/20/87 285 0.014:0.003 01/27/87 285 0.02710.003 01/27/87 285 0.03010.003 02/03/87 285 0.010to.003 02/03/87 285 0.00910.003 02/10/87 280 0.03710.004 02/10/87 285 0.04210.004 02/17/87 290 0.01410.003 02/17/87 290 0.01710.003 02/24/87 285 0.01010.003 02/24/87 285 0.01210.003 03/03/87 285 0.02010.003 03/03/87 285 0.02210.003 03/10/87 285 0.01210.003 03/10/87 285 0.01310.003 03/17/87 280 0.00510.003 03/17/87 280 0.00710.003 03/24/87 280 0.005t0.003 03/24/87 285 0.00510.003 03/31/87 285 0.01010.003 03/31/87 285 0.00910.003 04/07/87 280 0.01710.003 04/07/87 285 0.01010.003 04/14/87 230 0.01110.003 04/14/87 285 0.01010.003 04/21/87 285 0.00910.003 04/21/07 285 0.00510.003 04/28/87 285 0.01410.003 04/28/87 285 0.01910.003 05/05/87 285 0.01310.003 05/05/87 285 0.01210.003 05/12/87 285 0.00410.003 05/12/87 285 0.00410.003 05/19/87 285 0.01110.003 05/19/87 285 0.01110.003 05/26/87 285 0.01310.003 05/26/87 285 0.01010.003 06/02/87 65(a) 0.00810.003 06/02/87 285 0.00410.003 06/09/87 285 0.013t0.003 06/09/87 285 0.010io.003 06/16/87 290 0.01110.003 06/16/87 285 0.00010.003 06/23/87 285 0.00510.003 06/23/87 285 0.006!0.003 06/30/87 275 0.01110.003 06/30/87 280 f.01110.003 07/07/87 285 0.00810.003 07/07/87 285 0.00ft0.003 07/14/87 295 0.00010.003 07/14/87 290 0.00710.003 07/21/87 285 0.006to.003 07/21/87 285 0.009 0.003 07/28/87 280 0.01010.003 07/28/87 285 0.00910.003 08/04/87 245 0.01010.003 08/04/87 285 0.01210.003 08/11/87 285 0.01210.003 08/11/87 285 0.01110.003 08/18/87 290 0.00710.003 08/18/87 290 0.00810.003 08/25/87 280 0.01010.003 08/25/87 285 0.01010.003 09/01/87 285 0.01810.003 09/01/87 285 0.02110.003 09/08/87 285 0.01610.003 09/08/87 285 0.01310.003 09/15/87 280 0.01310.003 09/15/87 285 0.01310.003 09/22/87 285 0.01210.003 09/22/87 290 0.01510.003

  • Iodine cartridge concentrations are <0.05 unless otherwise noted.

(a) Timer failure on monitoring unit.

+ l s i TABLE 5-1 Sheet 4 of 7 f AIRBORNE 10 DINE-131* AND CROSS BETA IN AIR PARTICULATE FILTERS  !

(Weekly Collections)

\

Location 68* Location 1188  !

Collection Volume Cross 8 Collection Volume Cross 8 i Date (m3 ) (oci/m3) ,

Date 3

_(m ) (DCL/m3 )

i 09/29/87 285 0.01810.003 09/29/87 285 0.02110.003 10/06/87 285 0.02410.003 10/04/87 285 0.02510.003 10/13/87 285 0.02810.003 10/13/87 285 0.02610.003 10/20/87 285 0.02010.003 10/20/87 285 0.02010.003 1 10/27/47 285 0.02710.003 10/27/87 285 0.03210.004 l 11/03/87 290 0.02110.003 11/03/87 285 0.02610.003 l 11/10/87 280 0.02210.003 11/10/87 285 0.02210.003 11/17/87 11/17/87 285 0.01110.003 285 0.01110.003

! 11/24/87 285 0.01810.003 11/24/87 285 0.01910.003 12/01/87 285 0.01210.002 12/01/87 285 0.01210.002 12/08/87 285 0.00410.003 12/08/87 285 0.00610.003 l 12/15/87 285 0.00910.003 12/15/87 290 0.00910.003 1 12/22/87 285 0.01910.003 12/22/87 285 0.02110.003 ,

12/29/87 280 0.01810.003 12/29/87 285 0.01610.003 i

  • Iodine cartridge concentrations are <0.05 unless otherwise noted.

i i

f l

i i

i l L i

i

\

I i

1 l

l i

1 1

4 TABLE 5-1 Sheet 5 of 7 l

AIRBORNE 10 DINE-131* AND CROSS BETA IN AIR PARTICULATE FILTERS I (Weekly Collections)

Location 14* Location 2*

Collection Volume Gross B Collection Volume Cross B 3 (pC1/m 3) Date 3 (m ) _(pci/m 3)

Date (m )

01/06/87 285 0.00710.003 01/06/87 285 0.00510.003 01/13/87 285 0.03110.004 01/13/87 285 0.02410.003 01/20/87 285 0.01310.003 01/20/87 285 0.01110.003 01/27/87 285 0.02710.003 01/27/87 285 0.02410.003 02/03/87 285 0.01010.003 02/03/87 285 0.01010.003 02/10/87 280 0.03410.004 02/10/87 280 0.03610.004 02/17/87 290 0.01410.003 02/17/87 290 0.01310.003 j 02/24/87 285 0.00910.003 02/24/87 285 0.01110.003 l 03/03/87 285 0.02310.003 03/03/87 285 0.01810.003 03/10/87 285 0.01410.003 03/10/87 285 0.01210.003 03/17/87 280 0.00410.003 03/17/87 280 0.00710.003 03/24/67 285 0.00610.003 03/24/87 285 0.00610.003 03/31/87 285 0.01310.003 03/31/87 285 0.01710.003 04/07/87 285 0.01410.003 04/07/87 285 0.02310.003 04/14/87 285 0.01010.003 04/14/87 285 0.01210.003 04/21/87 285 0.00910 S03 04/21/87 285 0.00910.003 04/28/87 285 0.01910 '03 04/28/87 285 0.013t0.003 05/05/87 285 0.01410.003 05/05/87 285 0.00610.003 05/12/87 285 0.01710.003 05/12/87 285 0.00710.003 05/19/87 285 0.01110.003 05/19/87 285 0.01210.003 05/26/87 285 0.01110.003 05/26/87 285 0.01410.003 06/02/87 285 0.00510.003 06/02/87 285 0.00810.003 06/09/87 285 0.01110.003 06/09/87 285 0.01710.003 06/16/87 290 0.00610.003 06/16/87 290 0.01010.003 06/23/87 285 0.00510.003 06/23/87 285 0.00910.003 06/30/87 100(a) 0.01310.008 06/30/87 280 0.00910.003 07/07/87 285 0.00510.003 07/07/87 285 0.00610.003 07/14/87 290 0.01110.003 07/14/87 290 0.00610.003 07/21/87 285 0.00610.003 07/21/87 285 0.00710.003 07/28/87 280 0.00610.003 07/28/87 280 0.00610.003 08/04/87 285 0.00710.003 08/04/67 285 0.01010.003 08/11/87 285 0.01210.003 08/11/87 285 0.01210.003 08/18/87 290 0.00810.003 08/18/87 290 0.00710.003 08/25/87 280 0.01010.003 08/25/87 280 0.01010.003 09/01/87 285 0.01710.003 09/01/87 285 0.01810.003

, 09/08/87 125(a) 0.01910.003 09/08/87 285 0.01510.003 l 09/15/87 30(a) 0.03410.003 09/15/87 285 0.01210.003 09/22/87 285 0.01110.003 09/22/87 285 0.01410.003

  • Iodine cartridge concentrations are <0.05 unless otherwise noted.

(a) Loss of electrical power to monitoring unit.

o TABLE 5-1 Sheet,6 of 7 AIRBORNE 10 DINE-131* .'ND GROSS BETA IN AIR PARTICULATE FILTERS (Weekly Collections)

Location 14* Location 2*

Collection Volume Gross 8 Collection Volume Gross 8 Date (m3 ) (oci/m 3) Date (m3 ) (pCi/m 3) 09/29/87 285 0.01610.003 09/29/87 285 0.01710.003 10/06/87 285 0.01710.003 10/06/87 285 0.02210.003 10/13/87 280 0.02510.003 10/13/87 275 0.03110.004 10/20/87 285 0.02010.003 10/20/87 285 0.01810.002 10/27/87 285 0.02410.003 10/27/87 285 0.02810.003 11/03/87 290 0.02010.003 11/03/87 290 0.02110.003 11/10/87 285 0.02110.003 11/10/87 280 0.02010.003 11/17/87 285 0.01010.003 11/17/87 285 0.01310.003 11/24/87 285 0.01610.003 11/24/87 285 0.01810.003 12/01/87 285 0.00910.002 12/01/87 285 0.01010.002 12/08/87 285 0.00610.003 12/08/87 285 0.00510.003 12/15/87 290 0.00910.003 12/15/87 290 0.00910.003 12/22/87 285 0.01810.003 12/22/87 285 0.01610.003 12/29/87 285 0.01710.003 12/29/87 285 0.01410.003

  • Iodine cartrid5e concentrations are <0.05 unless otherwise noted, s

O TABLE 5-1 Sheet 7 of 7 AIRBORNE IODINE-131* AND CROSS BETA IN AIR PARTICULATE FILTERS (Weekly Collections)

Location 19* Location 19* ,

Collection Volume Gross B Collection Volume Gross B Date (m3 ) (DCi/m3 ) Date (m3 ) (pC1/m 3) 01/06/87 285 0.00910.003 07/07/87 285 0.00710.003 01/13/87 285 0.02510.003 0?/14/8? 285 0.00810.003 01/20/87 285 0.01410.003 07/21/87 285 0.010i,0.003 01/2*//87 285 0.02210.003 07/28/87 285 0.01110.003 02/03/87 285 0.01110.002 08/04/87 285 0.01010.003 02/10/87 290 0.034t0.004 08/11/87 285 0.01310.003 02/17/87 280 0.01110.003 08/18/87 285 0.01010.003 02/24/87 285 0.01210.003 08/25/87 290 0.01210.003 03/03/87 285 0.01810.003 09/01/87 285 0.02110.003 ,

03/10/C7 285 0.01210.003 09/08/87 285 0.01910.003 03/17/87 285 0.00510.003 09/15/87 285 0.01510.003 03/24/87 285 0.00510.003 09/22/87 285 0.02010.003 03/31/87 280 0.01410.003 09/29/87 285 0.01610.003  ;

04/07/87 285 0.00910.003 10/06/87 285 0.02010.003 04/14/87 285 0.01110.003 10/13/87 290 0.02710.003 04/21/87 285 0.00610.003 10/20/87 285 0.01910.003, 04/28/87 285 0.02010.003 10/27/87 285 0.03110.003 05/05/87 285 0.01410.003 11/03/87 280 0.02810.003 05/12/c' 285 0.01810.003 11/10/87 290 0.02310.003 05/1^- 285 0.01310.003 11/17/87 285 0.01410.003 )

CJ 285 0.011to.003 11/24/87 285 0.016t0.003

06. . :s 285 0.00710.003 12/01/87 285 0.00910.003 06/09 87 285 0.01210.003 12/08/87 285 0.00310.003 j 06/16/87 280 0.01010.003 12/15/87 285 0.00910.003 l 06/23/87 285 0.00610.003 12/22/87 285 0.02110.004 06/30/87 290 0.01410.003 12/29/87 290 0.02010.003
  • Iodine cartridge concentrations are <0.05 unless otherwise noted.

TABLE 5-2

SUMMARY

- GROSS BETA IN AIR SAMPLES 4

pC1/m3 Averate Maximum Minish Trojan On: Ete Stations l

1F 0.01310.007 0.038 0.004 II 0.01410.008 0.042 0.004 Oregon Stations 2 0.01410.007 0.036 0.005 6B 0.01410.007 0.037 0.004 19 0.01510.007 0.034 0.003 Washington Stations 11B 0.01410.008 0.042 0.004 14 0.014 0.007 0.034 0.004 l

\,

o a

TABLE 5-3 CAMMA EMITTERS CONCENTRATIONS IN AIR PARTICULATE FILTERS (Quarterly Composites)

Collection (pCL/m3 /nuclide)

Date IF II 6B 11B 1st Quarter <0.05 <0.05 <0.05 <0.05 l

2nd Quarter <0.05 <0.05 <0.05 <0.05 3rd Quarter <0.05 <0.05 <0.05 <0.05 4th Quarter <0.05 <0.05 <0.05 <0.05 Collection (DCi/m3 /nuclide)

Date 14 2 19 l 1st Quarter <0.05 <0.05 <0.05 l

2nd Quarter <0.05 <0.05 < 0 . 0.s 3rd Quarter <0.05 <0.05 <0.05 4th Quarter <0.05 <0.05 <0.05

o a

TABLE 5-4 RADIOACTIVITY IN FOOD CROPS

[pci/g/nuclide (wet)]

Location l'I Sample Collection .

Type Date Camma Emitters Lettuce [a] 06/10/87 <0.02 Beets 06/10/87 <0.02 Carrots 07/15/87 <0.02 Swiss Chard 07/15/87 <0.02 Swiss Chard 08/05/87 <0.02 Carrots 08/05/87 <0.02 Blackberries 08/05/87 <0.02 Apples 08/31/87 <0.02 (a) Split with State of Oregon.

l l

)

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o e

TABLE 5-5 RADIOACTIVITY IN WELL WATER DCi/1 Collection Location 1G Location 3 Location 6B Ganna Gama Gama Date Tritium Emitters Tritium Emitters Tritium Emitters 03/11/87 <1000 <10 <1000 <10 <1000 <10 06/10/87 <1000 <10 <1000 <10 <1000 <10 09/09/87 <1000 <10 <1000 <10 <1000 <10 ,

12/09/87 <1000 <10 <1000 <10 <1000 <10

TABLE 5-6 Sheet 1 of 4 RADI0 ACTIVITY IN MILK l

pCi/1 Collection Location 17A Date I-131 Sr-89 Sr-90 Nuclides Y Emitters 01/05/87 <0.5 <1 1.211.2 <10 02/09/87 <0.5 <1 3.811.3 Cs-137 1914

  • 03/09/87 <0.5 <1 3.211.1 Cs-137 2613
  • 03/23/87 <0.5 <1 1.610.9 Cs-137 1413(*'

04/06/87 <0.5 <1 4.111.0 <10 04/20/87 <0.5 <2( 6.411.2 <10 05/04/87 <0.5 <2( 5.0+1.2

~

<10 l

05/18/87 <0.5 <1 2.111.0 <10 i 06/08/87 <0.5 <2 7.211.3 <10 06/22/87 <0.5 <1 5.311.2 <10 07/06/87 <0.5 <1 <1 <10 07/20/87 <0.5 <1 1.711.0 <10 08/03/87 <0.5 <1 4.311.2 <10 08/17/87 <0.5 <1 2.511.0 <10 08/31/87 <0.5 <1 2.410.7 <10 09/14/87 <0.5 <2 8.611.6 <10 09/28/87 <0.5 <1 0.810.8 <10 10/12/87 <0.5 <1 1.410.9 <10 10/26/87 <0.5 <1 2.811.0 <10 11/09/87 <0.5 <1 3.111.3 <10 11/23/87 <0.5 <1 3.611.1 <10 12/07/87 <0,5 <1 6.611.7 Cs-137 914 *

(a) All other gamma emmiters <10.

(b) Due to low chemical recovery.

(c) Due to low sample volume.

e a

TABLE 5-6 Sheet 2 of 4 pCL/1 Collection Location 19 Date I-131 Se-89 Sr-90 Nuclides Y Emitters 01/05/87 <0.5 <2 <1 <10 02/09/87 <0.5 <2 <1 Cs-137 812

  • 03/09/87 <0.5 <1 <1 <10 03/23/87 <0.5 <1 1.110.8 Co-137 912
  • 04/06/87 <0.5 <1 <1 <10 04/20/87 <0.5 <1 1.410.8 <10 >

05/04/87 <0.5 <1 <1 <10 05/18/87 <0.5 <1 <1 <10 06/08/87 <0.5 <1 <1 <10 06/22/87 <0.5 <1 2.210.9 <10 07/06/87 <0.5 <1 <1 <10 07/20/87 <0.5 <1 2.810.8 <10 08/03/87 <0.5 <1 0.910.8 <10 08/17/87 <0.5 <1 <1 <10 08/31/87 <0.5 <2 2.210.9 <10 09/14/87 <0.5 <1 1.610.8 <10 09/28/87 <0.5 <1 1.710.8 <10 10/12/87 <0.5 <1 0.610.5 <10 10/26/87 <0.5 <1 1.510.8 <10 11/09/87 <0.5 <1 <1 <10 11/23/87 <0.5 <1 <1 <10 12/07/87 <0.5 <1 <1 <10 (a) All other gamma emmiters <10.

(b) Due to low chemical recovery.

e TABLE 5-6 Sheet 3 of 4 pC1/1 Collection Location 68 Date I-131 Sr-89 Sr-90 Nuclides y Emitters 61/05/87 <0.5 <1 1.210.9 < 1LO 02/09/87 <0.5 <1 <1 Cs-137 1213(*'

03/09/87 <0.5 <1 1.110.9 Cs-137 1313(*

03/23/87 <0.5 <2 1.711.1 <10 04/06/87 <0.5 <1 <1 <10 l

04/20/87 <0.5 <1 <1 <10 l

05/04/87 <0.5 <2 <1 <10 05/18/87 <0.5 <1 <1 <10 {

06/08/87 <0.5 <2 3.311.1 <10 06/22/87 <0.5 <2 611.4 <10 07/06/87 <0.5 <1 1.811.3 <10 J7/20/87 <0.5 <2 1.5+0.9 <10 08/03/87 <0.5 <1 2.010.7 <10 k 08/17/87 <0.5 <1 0.910.5 <10 08/31/87 <0.5 <2 3.311.1 <10 09/14/87 <0.5 <1 2.210.7 <10 09/28/87 <0.5 <1 <1 <10 10/12/87 <0.5 <1 1.610.7 <10 10/26/87 <0.5 <1 1.010.8 <10 11/09/87 <0.5 <1 1.510.0 <10 11/23/87 <0.5 <1 1.410.9 <10 12/07/87 <0.5 <1 <1 <10 (a) All other gama emiters <10.

(b) Due to low chemical recovery.

t

e TABLE 5-6 Sheet 4 of 4 0C1/1 Collection Location 63 Date I-131 Sr-89 Sr-90 Nuclides y Emitters 01/05/87 <0.5 <1 1.010.8 <10 02/09/87 <0.5 <1 2.511.1 <10 03/09/87 <0.5 <2 3.110.9 Cs-137 3214

  • 03/23/87 <0.5 <1 4.311.2 Cs-137 1713 Cs-134 1213 04/06/87 <0.5 <1 1.0io.9 Cs-137 2713
  • 04/20/87 <0.5 <2 6.711.2 Cs-137 3613 Cs-134 1013 05/04/87 <0.5 <1 1.511.0 Cs-137 4014 Cs-134 2014 05/18/87 <0.5 <1 2.411.1 Cs-137 4014(*'

06/08/87 <0.5 <1 '3.311.1 Cs-137 3915

  • 06/22/87 <0.5 <2 13.011.4 <10 07/06/87 <0.5 <1 1.211.0 Cs-137 1113(*

07/20/87 <0.5 <1 7.711.4 Cs-137 813(*

08/03/87 <0.5 <1 2.610.9 <10 08/17/87 <0,5 <1 2.111.0 <10 08/31/87 <0.5 <2 5.211.0 <10 09/14/87 <0.5 <1 1.810.5 <10 09/28/87 <0.5 <1 4.611.2 <10 10/12/87 <0.5 <1 2.610.6 <10 10/26/87 <0.5 <1 5.011.2 <10 11/09/87 <0.5 <1 5.211.2 <10 11/23/87 <0.5 <1 5.211.2 <10 12/07/87 <0.5 <2 1.710.9 <10 (a) All other gamma emiters <10.

(b) Due to low chemical recovery.

s e

i TABLE 5-7 Shtst 1 of 2 AMBIENT GAMMA RADIATION LEVELS FOR 1987 mR/ Day (Mean Daily Exposure 12o Error)

First Quarter Second Quarter Third Quarter Fourth Quarter Site 02/11/87-05/13/87 C5/13/87-08/13/87 08/13/87-11/11/87 11/11/87-02/10/88 1A 0.1010.01 0.0910.02 0.1110.02 l

la 0.1110.02 0.10io.02 0.1210.02 0.1410.04 l ic 0.1210.02 0.12io.02 0.1410.02 0.1510.05 1E 0.0910.01 0.0910.02 0.1110.02 0.1210.04 1F 0.1310.02 0.1210.02 0.1510.03 0.1410.05 1H 0.1610.03 0.2710.06 0.1810.04 0.2010.07 II 0.12 0.02 0.1010.02 0.12io.02 0.1410.05 IJ 0.10io.02 0.1010.02 0.1110.02 0.1310.04 2 0.15 0.02 0.1510.03 0.17io.03 0.1810.06 3 0.1410.02 0.1510.03 0.17io.03 0.1810.06 4c 0.1210.02 0.1310.03 0.15 0.03 0.15+0.05 6B 0.1110.02 0.1210.02 0.1410.03 0.1410.04 11A 0.1110.02 0.1210.03 0.1210.02 0.1110.02 20

  • 0.1010.02 0.1010.02 0.1210.04 21 0.0910.01 0.0810.02 0.1010.02 0.1110.04 22 0.10+0.01 0.09+0.02 -

0.12+0.02 0.12+0.04 l

l 23 0.11+0.02 0.11+0.02 -

0.12+0.02 0.13+0.04 I

24 0.16+0.02 0.15+0.03 0.17+0.03 0.18+0.07 l l

25 0.13io.02 0.1210.02 0.1410.03 0.1410.06 1 26 0.1610.02 0.1610.02 0.1710.03 0.1810.06 27 0.16 0.03 0.1810.04 0.2010.04 0.1910.07 28 0.1610.03 0.1710.04 0.1910.04 0.1910.07 29 0.1710.03 0.1710.04 0.1910.04 0.1910.07 30 0.1710.03 0.1610.02 0.1810.04 0.18io.06 31 0.15io.02 0.1510.03 0.1610.03 0.1810.06 32 0.1410.02 0.1210.03 0.1410.03 0.1610.05 33 0.1610.03 0.1510.03 0.17io.03 0.1710.06

  • Dosimeter vandalized during monitoring period.

e

'O TABLE 5-7 Sheet 2 of 2 First Quarter Second Quarter Third Quarter Fourth Quarter Site 02/11/87-05/13/87 05/13/87-08/13/87 08/13/87-11/11/87 11/11/87-02/10/88 34 0.1610.02 0.1410.03 0.1510.03

  • 35 0.1310.02 0.1310.03 0.1410.03 0.17 io.06 36 0.1710.03 0.1410.03 0.1510.03 0.1610.06 37 0.1610.03 0.1510.03 0.1710.03 0.17 0.06 38 0.1310.02 0.1110.02 0.1210.02 0.1410.05 39 0.1710.03 0.16io.04 0.1810.04 0.1810.07 40 0.11 0.02 0.1119 02 0.13to.02 0.1110.03 41 0.12ip.03 0.1210.03 0.1310.02 0.1210.03 42 0.1110.02 0.11io.02 0.1310.02 0.1110.03 43 0.1210.03 0.1319.03 0.1410.03 0.1219 03 44 0.1310.03 0.1310.03 0.1510.03 0.1310.04 45 0.13to.03 0.1310.03 0.1510.03 0.1210.03 46 0.1110.02 0.12io.02 0.1210.02 0.1010.03 47 0.1210.03 0.1210.02 0.1210.02 0.1210.03 48 0.12 ,0.03 0.11io.02 0.13 0.02 0.1210.03 49 0.0910.02 0.1010.02 0.1110.02 0.1110.03 50 0.1110.02 0.1010.02 0.11 0.02 0.1110.03 51 0.12 0.03 0.1210.02 0.13 ,0.02
  • 52 0. 310.02
  • 0.1110.02 0.1219 03 53 0.1110.02 0.1110.02 0.1210.02 0.11t0.03 54 0.1610.04 0.1710.04 0.1910.04 0.1710.05 55 0.11io.02 0.1110.02 0.1210.02 0.12to.03 56 0.07io.01 0.06 0.01 0.0819 01 0.0810.03 57 0.1310.03 0.1310.02 0.1510.03 0.1310.04 58 0.1410.03 0.1310.02 0.1510.03 0.1310.04 59 0.1010.02 0.1010.02 0.1110.02 0.1010.03 60 0.1110.02 0.1110.02 0.1210.02 0.1110.03 61 0.1410.03
  • 0.1610.02 0.1110.03 62 0.0710.01 0.05io.01 0.0810.01 0.0810.02 64 0.1210.02 0.11 0.02 0.1310.02 0.1410.05
  • Dosimeter vandalized during monitoring period.

TABLE 5-8 ,

l RADIOACTIVITY IN DRINKING WATER Location 2 - Rainier Municipal Water Supply Location 66 - St. Ifelens' Municipal Water Supply pC1/1 pC1/1 Gamma Gamma Collection Dates Cross Beta Tritium Emitters Collection Dates Cross Beta Tritium Emitters 01/05/87-02/02/87 2.011.0 <1000 <10 01/05/87-02/02/87 3.311.1 <1000 <10 02/02/87-03/02/87 1.711.0 <1000 <10 02/02/87-03/02/87 4.011.2 <1000 <10 03/02/87-04/06/87 3.611.0 <1000 <10 03/02/87-04/06/87 4.611.4 <1000 <10 04/06/87-05/04/87 1.811.0 <1000 <10 04/06/87-05/04/87 3.511.1 <1000 <10 05/04/87-06/01/87 3.011.1 <1000 <10 05/04/87-06/01/87 4.511.1 <1000 <10 06/01/87-07/06/87 2.011.0 <1000 <10 06/01/87-07/06/87 2.211.0 <1000 <10 07/06/87-08/03/87 1.711.0 <1000 <10 07/06/87-08/03/87 3.011.1 <1000 <10 08/03/87-08/31/87 3.111.0 <1000 <10 08/03/87-08/31/87 3.711.0 <1000 <10 08/31/87-10/05/87 3.711.0 <1000 <10 08/31/87-10/05/87 2.811.6 <1000 <10 10/05/87-11/02/87 2.611.0 <1000 <10 10/05/87-11/02/87 4.111.1 <1000 <10

~

11/02/87-12/07/87 6.911.3 <1000 <10 11/02/87-12/07/87 5.611.3 <1000 <10 12/07/87-01/05/88 5.911.2 <1000 <10 12/07/87-01/05/88 4.211.1 <1000 <10 A

9 TABLE 5-9 RADIOACTIVITY IN SHORELINE SOIL pCi/g/nuclide (dry) b Location CR3 Collection Gamma Date Emitters 03/11/87 <0.1 09/02/87 <0.1 l

. I

s TABLE 5-10 RADIOACTIVITY IN FISH / INVERTEBRATES pC1/g/nuclide (wel)

Collection Location Date Species Camma Emitters CR3 03/12/87 Rainbow Trout (Steelhead) <0.1 1A 03/12/87 Northern Squawfish (14), <0.1 Yellow Perch (6) 1D 03/19/87 Bluegill (1), Yellow Perch (2), <0.1 Largemouth Bass (1), Carp (2)

CR3 05/29/87 Crayfish <0.1 CR3 09/03/87 Chinook Salmon * <0.1 1A 09/04/87 Largemounth Basr (1), Carp (1), <0.1 Bridgelip Sucker (1) 1D 09/04/87 Yellow Perch (1), Smallmouth <0.1 Bass (8), Largemouth Bass (1),

Carp (1)

CR3 10/09/87 Crayfish <0.1 (a) Split sample with State of Oregon.

rWL, adL _ _

l

- mumm

~

Portland General BectricCompany David W. Cockfield Vice President, Nuclear April 29, 1988 Trojan Nuclear Plant Docket 50-344 License NPF-1 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555

Dear Sir:

Radiological Environmental Monitoring Report Enclosed is one copy of the Portland Cenoral Electric Company's 1987 Operational Environmental Radiological Survoillance Program Annual Report, PGE-1006-87, for the Trojan Nuclear Plant.

Sincerely, L

Enclosure c: Mr. John B. Martin Mr. Ray D. Paris, Manager (2 oncl.)

Regional Administrator, Region V Radiation Control Section U.S. Nuclear Regulatory Commission Oregon State Health Division Mr. George Knighton Mr. Jerry Loitch Director, PWR-A Radiation Representative Project Directorate No. V U.S. Environmental Protection Agency l

Mr. William Dixon Mr. Robert. R. Mooney, Supervisor State of Oregon Radiation Control Section I Department of Energy Washington Social and Health Services 1 Mr. R. C. Bare NRC Resident Inspector Trojan Nuc1 car Plant th \

\ \

121 S W Sa tron Stwt Por'anci Cregrn 97204 i

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